IR 05000354/2018010
| ML18212A283 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/30/2018 |
| From: | Mel Gray Engineering Region 1 Branch 1 |
| To: | Sena P Public Service Enterprise Group |
| References | |
| IR 2018010 | |
| Download: ML18212A283 (14) | |
Text
July 30, 2018
SUBJECT:
HOPE CREEK GENERATING STATION UNIT 1 - DESIGN BASES ASSURANCE INSPECTION (TEAMS) REPORT 05000354/2018010
Dear Mr. Sena:
On June 22, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Generating Station (HCGS). The NRC inspectors discussed the results of this inspection with John Garecht, Hope Creek Maintenance Director, and other members of your staff. The final results of the inspection were presented via telephone on July 6, 2018, to David Mannai, Senior Director Regulatory Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any findings or more-than-minor violations.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety
Docket No.: 50-354 License No.: NPF-57
Enclosure:
Inspection Report 05000354/2018010
Inspection Report
Docket Number:
50-354
License Number:
Report Number:
Enterprise Identifier: I-2018-010-0035
Licensee:
Facility:
Hope Creek Generating Station (HCGS)
Location:
Hancocks Bridge, NJ 08038
Inspection Dates:
April 16 to May 4, 2018
Inspectors:
A. Patel, Senior Reactor Inspector (Team Lead), Division of
Reactor Safety (DRS)
K. Mangan, Senior Reactor Inspector, DRS
N. Floyd, Senior Reactor Inspector, DRS
J. Brand, Reactor Inspector, DRS
M. Yeminy, NRC Contractor
N. Della Greca, NRC Contractor
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring PSEGs performance at
Hope Creek Generating Station by conducting a team design bases assurance inspection in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
No findings or more-than-minor violations were identified.
INSPECTION SCOPES
This inspection was conducted using the appropriate portions of the inspection procedure (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components, permanent modifications, and operating experience during the weeks of June 4 and June 18, 2018.
For the components, the team reviewed the attributes listed in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations. Specific documents reviewed are listed in the Documents reviewed section.
Components===
- Station Auxiliary Cooling System to Residual Heat Removal Heat Exchanger Return Isolation Valve, EG-HV-2512A.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results The team used Appendix B guidance for Valves, Instrumentation, and Electrical Loads.
- Reactor Core Isolation Cooling Turbine.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results The team used Appendix B guidance for Valves, Instrumentation, and Pumps (as applicable to turbine operation).
- A Emergency Diesel Generator mechanical components.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results
The team used Appendix B guidance for Electric Loads.
- B Emergency Diesel Generator electrical components.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results The team used Appendix B guidance for Electric Loads.
- A Residual Heat Removal Pump.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results The team used Appendix B guidance for Pumps, Valves, and Instrumentation.
Component, Large Early Release Frequency (1 Sample)
- RCIC Exhaust Check Valve, H1FC-1-FC-V003.
o Material condition and installed configuration (e.g., visual inspection during a walkdown)o Normal, abnormal, and emergency operating procedures o Consistency between documentation (e.g., procedures)o Component/system health reports, corrective maintenance effectiveness and records, and corrective action history o Design calculations o Surveillance testing and recent test results The team used Appendix B guidance for Valves.
Permanent Modifications (4 Samples)
- C Emergency Diesel Generator intercooler pump flexible hose support modification
- Revise emergency operating procedure calculation, H-1-ZZ-MDC-4019, to reflect reactor fuel changes
- Motor Control Center compartment replacements
- High Pressure Coolant Injection system battery analysis
Operating Experience (3 Samples)
- NRC IN 2016-05, Operating Experience Regarding Complications from Loss of Instrument Air, dated April, 27 2016
- NRC Regulatory Issue Summary 2011-12, Adequacy of Station Electric Distribution System Voltages, Revision 1
- NRC IN 2009-09 - Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify, dated June,
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 22, 2018, the team debriefed the Design Bases Assurance Inspection (Teams)preliminary results to Mr. John Garecht, Hope Creek Maintenance Director, and other members of PSEG staff.
- On July 6, 2018, the team conducted a phone exit presenting the final results of the inspection with Mr. David Mannai, Senior Director Regulatory Operations, and other members of PSEG staff.
DOCUMENTS REVIEWED
71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)
Calculations
1-P-KJ-624-C010, Design Calculation for Emergency Diesel Generator (EDG) Surge/Vent
Anchors, Rev. 0
BC-0002(Q), NPSH for RHR Pumps with Suction from the Suppression Pool, Rev. 5
BC-0023(Q), RHR Min Flow Orifice E/1-D001, Rev. 3
BC-11(Q), RHR Minimum Flow Bypass Line Size, Rev. 2
BC-3(Q), NPSH for RHR Pumps in Shutdown Cooling Mode, Rev. 3
BD-0001, NPSH for RCIC System Pump, Rev. 4
BD-0003, RCIC Hydraulic Analysis, Rev. 6
C-1991, EDG Intercooler Pump Surge Piping, Rev. 0
C-1992, EDG Intercooler Pump Vent Piping, Rev. 0
DEH-09-0141, HPCI Steam Exhaust Piping Water Hammer Analysis, Dated 10/8/09
E-1.3 (Q), Hope Creek Generating Station Short Circuit Study of 480FV Systems, Rev. 3
E-1.4 (Q), HC Class 1E 125 & 250 VDC Systems Short Circuit and Voltage Drop Studies,
Rev. 7
E-15.1 (Q), Hope Creek Load Flow and Degraded Voltage Analysis, Rev. 7 & Rev. 11
E-18, Selection of Overload Heaters for AC MOVs and Continuous Duty Motors, Rev. 2
E-26 (Q), Breaker to Fuse & Fuse to Fuse Coordination for Appendix R, Rev. 4B
E-5.1 (Q), HC Class 1E 250 VDC Station Battery and Charger Sizing, Rev. 9
E-5.19 (Q), 250 VDC HPCI System Battery Analysis, Rev. 0
E-7.12 (Q), HC AVR Limits and Protection Coordination, Rev. 0
E-7.13 (Q), Penetration Assembly Protection, Rev. 4B
E-7.4 (Q), E-7.4(Q) Class 1E 4.16 KV System Protection Relay Settings, Rev. 6
E-7.7 (Q), Class 1E 480 V System Protecting Relaying, Rev. 7C
E-9 (Q), Standby Class 1E Diesel Generator Sizing, Revs. 9, 9A, & 9B
GM-0027, Diesel Generator Area HVAC Analysis, Rev. 1
H-1-EG-MDC-0938, MOV Capability Assessment for 1EG-HV-2512A, Rev. 1
Hope Creek Load Flow and Degraded Voltage Analysis, Rev. 11
MIDAS 2015.226, MIDACALC Results 1BD-HV-F046 DC Motor Operated Valve, Rev. 5
NAI-1484-01, Loads on Turbine Exhaust Pipes due to Post LOCA Turbine Trip, Rev. 1
SC-JE-0059, Diesel Fuel Oil Day Tank Level, Rev. 4
Corrective Action Documents (*initiated in response to inspection)
20411602
20466535
20519905
20529533
20594384
20595967
20601216
20602340
20613232
20613929
20628456
20629808
20633331
20633802
20663859
20665454
20667174
20686017
20686398
20689441
20696918
20698578
20701108
20721062
20723443
20725078
20736860
20738706
20738711
20746795
20747160
20750168
20751715
20754048
20754048
20754162
20760634
20761521
20764634
20767192
20769250
20769250
20769459
20771585
20772476
20772476
20780884
20784381
20784382
20786607
20786624
20787622
20790172
20791131
20791132
20791133
20791142
20791715
20796656
20796705*
20796837*
20796838*
20796847*
20796862*
20796875*
20796917*
20796918*
20796929*
20796941*
20796985*
20797040*
20797126*
20797498*
20798740
20798770*
20798781*
20798784*
20798786*
20798816
20798816
20798937*
20798940*
20798985*
20798986*
20799011*
20798816*
20799124*
20799129*
20799131*
20799402*
Design and Licensing Basis
Docket No, 50-354, Hope Creek Generating Station, Amendment to Facility Operating License,
Amendment No. 144
Drawings
1-P-FC-003, Fab Isometric RCIC Turbine Supply and Exhaust Reactor Building, Rev. 13
1-P-FC-01, System Isometric Reactor Building RCIC Turbine Supply and Exhaust, Rev. 19
10855-J200 (Q)-595, Logic Diagram, 4.16 KV Sys., Diesel Generator Circuit Breaker
(I) 52-40207, Rev. 15
10855-J200 (Q)-949, Logic Diagram, 862 Sys., Diesel Generator (I) DG800 Control (1 of 3),
Rev. 7
10855-M (Q) 366 (1), Sh. 1 of 30, Elect. Schematic, Engine Control, Rev. 17
10855-M (Q) 366 (2), Sh. 2 of 30, Elect. Schematic, Engine Control, Rev. 12
10855-P-0570, Sh. 15, Welding and Non Destructive Testing Requirements for Field Erected
Piping, Rev. 7
AM 88-1, Sht. 1, PID Auxiliary Building Diesel Area Control Diagram, Rev. 15
E-0001-0 (Q), Single Line Diagram, Station, Rev. 24
E-0006-1 (Q), Sh. 1 of 2, Single Line Meter & Relay Diagram, 4.16 KV Class 1E Power System,
Rev. 13
E-0006-1 (Q), Sh. 2 of 2, Single Line Meter & Relay Diagram, 4.16 KV Class 1E Power System,
Rev. 11
E-0008-1 (Q), Sh. 2 of 2, Single Line Meter & Relay Diagram, Diesel Generators, Rev. 4
E-0009-1 (Q), Sh. 1, Single Line Meter & Relay Diagram, 125 VDC System, Channels A & C,
Rev. 26
E-0009-1 (Q), Sh. 2, Single Line Meter & Relay Diagram, 125 VDC System, Channels B & D,
Rev. 30
E-0009-1 (Q), Sh. 4, Single Line Meter & Relay Diagram, 125 VDC System, Channels C & D,
Rev. 13
E-0018-1 (Q), Sh. 1 of 3, Single Line Meter & Relay Diagram, 480 Volt Class 1E Unit Substation
10B410, 10B420, 10B430, 10B440, 10B450, 10B460, 10B470, 10B480, Rev. 36
E-0018-1 (Q), Sh. 2, Single Line Meter & Relay Diagram, 480 Volt Class 1E Unit Substation
10B410, 10B420, 10B430, 10B440, 10B450, 10B460, 10B470, 10B480, Rev. 40
E-0019-1 (Q), 480 Volt MCC Tabulation Class 1E - Aux. Bldg. - D/G Area 10B411, 10B421,
10B431, 10B441, Rev. 13
E-0019-1 (Q), Sh. 2, 480 Volt MCC Tabulation Class 1E - Aux. Bldg. - D/G Area 10B411,
10B421, 10B431, 10B441, Rev. 15
E-0020-1 (Q), Sh. 1 of 2, 480 Volt MCC Tabulation Class 1E - Aux. Bldg. - D/G Area 10B451,
10B461, 10B471, 10B481, Rev. 17
E-0020-1 (Q), Sh. 2, 480 Volt MCC Tabulation Class 1E - Aux. Bldg. - D/G Area 10B451,
10B461, 10B471, 10B481, Rev. 13
E-0021-1 (Q), Sh. 1 of 6, 480 Volt MCC Tabulation, Class 1E MCC - Reactor Area 10B212,
10B222, 10B232 & 10B242, Rev. 55
E-0046-1 (Q), Schematic Meter & Relay Diagram, 4.16 KV Class 1E Station Power System,
Switchgears 10A401 & 10A403, Rev. 8
E-0047-1 (Q), Schematic Meter & Relay Diagram, 4.16 KV Class 1E Station Power System,
Switchgears 10A401 & 10A403, Rev. 7
E-0070-0 (Q), Electrical Schematic Diagram, Class 1E 4.16 KV Sta. Pwr. Sys. Swgr., Main
Circuit Breaker (I) 52-40201, Rev. 8
E-0071-0 (Q), Electrical Schematic Diagram, Class 1E 4.16 KV Sta. Pwr. Sys. Swgr., Main
Circuit Breaker (I) 52-40208, Rev. 8
E-0081-0 (Q), Electrical Schematic Diagram, Class 1E - 4.16 KV Unit Substa. Xfmr. Feeder,
Circuit Breaker (I) 52-40203, Rev. 5
E-0085-0 (Q), Electrical Schematic Diagram, Class 1E - 4.16 KV Sta. Pwr. Sys. Swgr., Diesel
Gen. Circuit Brkr. (I) 52-40207, Rev. 11
E-0208-0 (Q), Sh. 2, Electrical Schematic Diagram, Class 1E - 4.16 KV Circuit Breaker Control
Station Service Water Pump, Rev. 12
E-0223-0, Sh. 1, RHR HX Outlet Valve 1-HV-2512A Scheme No. 1C0318, Rev. 5
E-3060-0 (Q), Logic Diagram, Class 1E Station Pwr. Swgr. - 4.16 KV System, Main Circuit
Breaker, Rev. 16
E-3061-0 (Q), Logic Diagram, Class 1E Station Pwr. Swgr. - 4.16 KV System Unit Substa.
Xfmr. Feeder Circuit Breaker, Rev. 66
E-3080-0 (Q), Sh. 1 of 2, Logic Diagram, Class 1E Sta. Pwr. Swgr. - 4.16 KV System, Diesel
Generator Circuit Breaker, Rev. 12
E-3080-0 (Q), Sh. 2 of 2, Logic Diagram, Class 1E Sta. Pwr. Swgr. - 4.16 KV System, Diesel
Generator Circuit Breaker, Rev. 8
E-3081-0 (Q), Sh. 1 of 2, Logic Diagram, Diesel Generator Control, Rev. 7
E-3081-0 (Q), Sh. 2 of 2, Logic Diagram, Diesel Generator Control, Rev. 10
FSK-P-1-KJ-622, Small Piping/Aux Building Diesel Generator C from CG-400 to Tank C-407,
Rev. 13
FSK-P-1-KJ-624, Small Piping/Aux Building Diesel Generator C from Tank CT-407 to CG-400,
Rev. 17
J-10-0 (Q), Sh. 4, Logic Diagram, Station Service Water System, SSWS Pumps BP502 &
DP502 Start, Rev. 15
J-10-0 (Q), Sh. 5, Logic Diagram, Station Service Water System, SSWS Pumps BP502 &
DP502 Stop, Rev. 12
J-51-0, Sht. 16, Logic Diagram Residual Heat Removal, Rev. 7
J-107-0 (Q), Sh. 4, Logic Diagram, Emergency Load Sequencer, Rev. 3
J-4049-0. Sh. 2, Reactor Core Isolation Cooling RCIC Pump Turbine Control, Rev. 7
M-0910-0, Sh. 1, Process Flow Diagram Safety & Turbine Auxiliaries Cooling, Rev. 2
M-11-1, Sh. 1, Safety Auxiliaries Cooling Reactor Building, Rev. 32
M-30-1, Sh. 2, Diesel Generator Auxiliary Systems Intercooler and Injector Cooling, Jacket
Water, Crankcase Vacuum Air Intake, Exhaust and Vibration Monitoring Systems,
Rev. 27
M-49-1, Reactor Core Isolation Cooling, Rev. 30
M-50-1, RCIC Pump Turbine, Rev. 33
M-51-1, Sht. 1, Residual Heat Removal, Rev. 51
M-51-1, Sht. 2, Residual Hear Removal, Rev. 45
M-85-1, Sht. 1, Auxiliary Building Diesel Area Air Flow Diagram, Rev. 19
N-749, RHR Pump Head Capacity Curve, Rev. 0
N-1223, SACS Pump Curve, Rev. 0
Functional, Surveillance and Modification Acceptance Testing
280950, 24M PM Calibration 1KJSS-421B: B EDG Speed Switch, Performed on 2/14/17
50003496, Emergency Diesel Generator Interdependence Verification Test - 10 Year,
Performed on 4/21/09
50065569, 60M ST / 10-D-421, Class 1E, Channel A, 250 Volt Battery Performance Test,
Performed on 4/19/09
50123056, 60M ST / 10-D-421, Class 1E, Channel A, 250 Volt Battery Performance Test,
Performed on 10/24/13
50162739, Integrated Emergency Diesel Generator 1BG400 Test - 18 Months, Performed on
4/24/15
50175271, EDG1BG400 - 24 Hour Operability Run and Hot Restart Test, Performed on 9/9/16
50175692, NUST 18M ST 52-40208, 4KV Swgr. Degraded Voltage Instrumentation Channel
Calibration & Functional Test, Performed on 11/2/16
50175732, NUST 18M ST 52-40201, 4KV Swgr. Degraded Voltage Instrumentation Channel
Calibration & Functional Test, Performed on 10/31/16
50175793, 4.16 KV Bus 10A402 Undervoltage Test and Return to Service - B Channel,
Performed on 4/18/18
50176377, NUST ST 18M Test, 10-D-421 Class 1E, Channel A, 250V Battery Service Test,
Performed 10/31/16
50188845, EDG1BG400 - 24 Hour Operability Run and Hot Restart Test, Performed on 3/13/18
50190557, NUST Perform IC-FT.PE-0006 on Load Sequencer Div-2, Performed on 4/15/18
50190581, NUST ST 18M Test, 10-D-421 Class 1E, Channel A, 250V Battery Service Test,
Performed on 5/3/18
50199618, ST / 10-D-421, 250 Volt Battery Quarterly Surveillance, Performed on 2/25/18
50199857, NUST 3M ST 10-A-402-01 / 4.16 KV Swgr Degraded Voltage, Performed on 2/17/18
50199858, NUST 3M ST 10-A-402-08 / 4.16 KV Swgr Degraded Voltage, Performed on 2/17/18
202110, NUST ST / 10-D-421, 250 Volt Battery Quarterly Surveillance, Performed on 4/1/18
202136, Emergency Diesel Generator 1BG400 Operability Test - Monthly, Performed on
4/30/18
203057, Emergency Diesel Generator 1BG400 Operability Test - Monthly, Performed on
5/16/18
203499, NUST 31D ST 10-D-421 Class 1E, Channel A, 250V Battery Test, Performed on
5/27/18
203541, Perform IC-FT.PE-0002 on Load Sequencer Div-2, Performed on 5/14/18
HC.MD-PM.FC-0001, Reactor Core Isolation Cooling Steam Turbine Inspection and PM,
performed 5/16/18
HC.MD-PM.FC-0003(Q), Reactor Core Isolation Cooling Turbine Exhaust Check Valve
Inspection & PM, performed 12/14/12
HC.OP-FT.KJ-0001 (Q), Emergency Diesel Generator 1AG400-Functional Test, performed
4/3/18
HC.OP-IS.BC-0001(Q), AP202 A Residual Heat Removal Pump In-Service Test, Rev. 50 -
Performed 4/9/18
HC.OP-IS.BD-0001, Reactor Core Isolation Cooling Pump-OP203-Inservice Test, peformed
2/23/18
HC.OP-IS.BD-0101(Q), Reactor Core Isolation Cooling System Valves - Inservice Test,
performed 3/6/17
HC.OP-IS.BD-0101(Q), Reactor Core Isolation Cooling System Valves - Inservice Test,
performed 3/20/18
HC.OP-IS.EG-0101, Safety Auxiliaries Cooling System - Subsystem A Valves - Inservice Test,
Performed 01/05/18
HC.OP-IS.EG-0102 (Q), Safety Auxiliary Cooling System-Subsystem B Valves-IST, performed
1/27/14
HC.OP-ST.BD-0003, RCIC Functional Verification-18 Months, performed 2/28/17
HC.OP-ST.EG-0001, SACS Flow Path Verification - Monthly, Performed 04/30/18
HC.OP-ST.KJ-0001 (Q), Emergency Diesel Generator 1AG400-Operability Test-Monthly,
performed 5/8/18
Miscellaneous
10866-J610-65-1, Self-Acting Pressure Regulator, dated 5/2/83
160607BP-01, Machinery Analysis Report for C EDG Jacket Water Piping, dated 06/07/16
70105083, Technical Evaluation for Hope Creek 4.16kV 1E Undervoltage Relay Scheme, dated
2/23/09
70183330, Apparent Cause Evaluation for C EDG Jacket Water Braided Hose Leak, Rev. 3
BWROG-TP-14-018, Beyond Design Basis RCIC Elevated Temperature Functionality
Assessment, Rev. 0
Instrument Calibration Data Report, RCIC Flow Control H1FC-FC-4158, dated 6/8/18
Program Health Report for Inservice Testing (IST), Q4 - 2017
Program Health Report for Motor Operated Valves (MOV), Q2 - 2017
System Health Report for Diesel Generator, Q2 - 2018
System Health Report for SACS & TACS, Q2 - 2018
Modifications and Design Changes
DCP 80090368, Modify EG-HV-2512A logic to allow valve to be throttled, Rev. 1
DCP 80095620, Motor Control Center (MCC) Compartment Replacements, Rev. 4
DCP 80114476, C Emergency Diesel Generator Governor Control System Replacement,
Rev. 0
DCP 80117790, Revise EOP Calculation H-1-ZZ-MDC-4019, Rev. 0
DCP 80119727, Emergency Diesel Generator Vibrations Piping and Support Adjustments,
Rev. 0
DCP 80120892, 250 VDC HPCI System Battery Analysis, Rev. 0
DCP 80121930, VAVF-0032, Diaphragm Valve Replacement, Rev. 0
Procedures
EP-HC-111-223, HCGS ECG - EAL Technical Basis, Rev. 2
EP-HC-111-222, HCGS ECG - EAL Technical Basis, Rev. 0
ER-AA-302-1007, MOV Limitorque Actuator Capability Determination Methodology, Rev. 7
HC.IC-DB.BD-0002, EG-M Control Box and Ramp Generator Signal Converter (RCIC), Rev. 1
HC.IC-DC.ZZ-0358(Q), Dynalco Controls Universal Speed Switch & Speed Transmitter
SST-2000 Series, Rev 0
HC.IC-FT.PE-0002(Q), Emergency Load Sequencer System, Diesel Generator B, 1BC428,
Rev. 9
HC.IC-FT.PE-0006(Q), Time Interval Test. Emergency Load Sequencer System, Diesel
Generator B, 1BC428, Rev.10
HC.IC-LC.FC-001, RCIC Turbine Speed Control System, Rev. 11
HC.MD-GP.ZZ-0015(Q), Battery Equalizing Charge, Rev 21, Rev. 22 and Rev. 23
HC.MD-ST.KJ-0001, Diesel Generator Technical Specification Surveillance and Preventative
Maintenance, Rev. 46
HC.MD-ST.PB-0003(Q), Class 1E 4.16 KV Degraded Voltage Monthly Instrumentation Channel
Functional Test, Rev. 28
HC.MD-ST.PB-0016(Q), Class 1E 4.16 KV Feeder Degraded Voltage 18 Month Instrumentation
Channel Calibration & Functional Test 10-A-40201, Rev. 6
HC.MD-ST.PB-0017(Q), Class 1E 4.16 KV Feeder Degraded Voltage 18 Month Instrumentation
Channel Calibration & Functional Test 10-A-40208, Rev. 7
HC.MD-ST.PJ-0001(Q), 250 Volt Weekly Battery Surveillance, Rev. 24
HC.MD-ST.PJ-0002(Q), 250 Volt Quarterly Battery Surveillance, Rev. 34 & Rev. 35
HC.MD-ST.PJ-0007(Q), 250 Volt Station Batteries Performance Discharge Test Using BCT-
2000 with Windows Software and Associated Surveillance Testing, Rev. 0 & Rev. 3
HC.MD-ST.PJ-0008(Q), 250 Volt Station Batteries 18 Month Service Test Using BCT-2000 with
Windows Software and Associated Surveillance Testing, Rev. 5
HC.MD-ST.ZZ-0009, Motor Operated Valve Thermal Overload Protection Surveillance, Rev. 21
HC.OP-AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System, Rev. 9
HC.OP-AB.ZZ-0135, Station Blackout//Loss of Offsite Power//Diesel Generator Malfunction,
Rev. 43
HC.OP-AR.ZZ-0006, Overhead Annunciator Window Box B1, Rev. 26
HC.OP-EO-ZZ-0103/4-FC, Reactor Building & Rad Release Control, Rev. 11
HC.OP-EO-ZZ-0106-FC, Primary Containment Control HPCI/RCIC Only, Rev. 0
HC.OP-EO-ZZ-0102-FC, Primary Containment Control, Rev. 13
HC.OP-IS.EG-0101, Safety Auxiliaries Cooling System - Subsystem A Valves - Inservice Test,
Rev. 56
HC.OP-SO.BC-0001, Residual Heat Removal System Operation, Rev. 54
HC.OP-SO-BD-0001, Reactor Core Isolation Cooling System Operation, Rev. 44
HC.OP-SO.EG-0001, Safety and Turbine Auxiliaries Cooling Water System Operation, Rev. 56
HC.OP-SO.GM-0001(Q), Diesel Area Ventilation System Operation, Rev. 21
HC.OP-SO.KJ-0001 (Q), Emergency Diesel Generator Operation, Rev. 74
HC.OP-ST.BD-0004, RCIC System Response Time and Flow Test - 18 Month, Rev. 9
HC.OP-ST.KJ-0002(Q), Emergency Diesel Generator 1BG400 Operability Test - Monthly,
Rev. 78
HC.OP-ST.KJ-0006(Q), Integrated Emergency Diesel Generator 1BG400 Test - 18 Months,
Rev. 47
HC.OP-ST.KJ-0009(Q), Emergency Diesel Generator Interdependence Verification Test - 10
Year, Rev. 9
HC.OP-ST.KJ-0015(Q), EDG1BG400 - 24 Hour Operability Run and Hot Restart Test, Rev. 36
HC.OP-ST.PB-0006(Q), 4.16 KV Bus 10A402 Undervoltage Test & Return to Service - B
Channel, Rev. 20
HC.OP-ST.PB-0016(Q), 4.16 KV Bus 10A402 Undervoltage Test - B Channel, Rev. 3
HC.OP-ST.SM-0006, PCIS/RCIC Isolation Functional Test, Rev. 15
MA-AA-723-300, Diagnostic Testing and Inspection of Motor Operated Valves, Rev. 9
Vendor Manuals
76J-10700-15, Aux. Building Diesel Area HVAC, Rev. 2
90192-802, Installation Operating and Maintenance Manual for Model 3472 Back Pressure
Dampers, Rev. A
G300E, Ventilating and Industrial Axial Fan by Buffalo Forge, Rev. A
GEH-1768G, Instructions, Undervoltage Relays, Types IAV54E, IAV54F, IAV54H, IAV55C,
IAV55F, IAV55H and IAV55J, dated 11/94
PNO-E11-4010-0362, Design Spec data Sheet, Rev. 13
PN1-ES1-C001-0055(I), Reactor Core Isolation Cooling Pump, Rev. 3
PN1-E11-C002-0051, Residual Heat Removal Pumps by Ingersol Rand, Rev. 4
VTD 324925, Crane Nuclear Butterfly Valve General Assembly, dated 08/09/01
VTD 324927, Design/Seismic Report for Crane Nuclear Butterfly Valve, dated 08/31/01
VTD 327450, Reactor Core Cooling Isolation System (RCIC) Turbine Speed Increase, Rev. 1
VTD 431207 (001), Nutherm International, Inc., JE/Diesel Fuel Oil Storage N41 Level Switches,
4/2/09
VTD 431259, Turbine Auxiliary Cooling System (TACS) Flow Balancing, dated 07/21/09
VTD 431640, MCC vendor Manual, Rev. 0
VTD 431990, Cutler Hammer Harsh Environment Qualification of Lights, Switches, Fuse and
Terminal Blocks, Rev. 0
VTD 431992, Cutler Hummer Harsh Environment Qualification of Molded Case Circuit
Breakers, Rev. 0
VTD 431993, Seismic Qualification Report on 480 VAC 5 Section Motor Control Center for Hope
Creek Generating Station, Rev. 1
VTD PN1-ES1-C002-0054, Terry Steam Turbine Company RCIC, Rev. 13
VTD PN1-ES1-C001-0055, Reactor Core Isolation Pump, Rev. 4
VTD PJ610Q-0067, Technical Manual Operation, Maintenance, Trouble-Shooting, Repair and
Installation Pressure Reducer Valve, Rev. 0
Work Orders
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